ML20057C271
| ML20057C271 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/22/1993 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20057C272 | List: |
| References | |
| 93-525, NUDOCS 9309280156 | |
| Download: ML20057C271 (3) | |
Text
VinoixtA Ei.ncinic Asia Powen COMI'ANY R ictiM oxn, Visco ax A 20261 September 22, 1993 U.S. Nuclear Regulatory Commission Serial No.93-525 Attention: Document Control Desk NL&P/WFR/MAE R2 Washington, D.C. 20555 Docket Nos.
50-338 50-339 License Nos. NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 EMERGENCY PLAN REVISION We have reviewed your letter of August 9,1993 regarding your review of the North Anna Emergency Plan (NAEP), Revision 14. Your expressed concern with the NAEP, Revision 14, pertains to the deletion of a specific indicator (acoustic monitoring) that could be used by a Control Room operator to determine if an Emergency Action Level (EAL) had been met.
Based on that concern, you have concluded that the effectiveness of the subject EAL has been reduced.
The EAL in question pertains to the failure of a safety or relief valve to close after pressure reduction. The enclosure to your letter stated that the removal of the i
acoustical monitoring indicator reduced the effectiveness of the EAL due to the removal of a positive indicator for valve position. It also stated that the combination of acoustical and temperature indicators, rather than temperature only, would provide the Control Room Operators with more prompt, adequate, and reliablo information to determine if an emergency should be declared.
As discussed with Mr. A. Gocden on September 21,1993, the EAL is documented in Emergency Manager Controlling Procedure EPIP-1.01 and the NAEP.
The Emergency Action Level Table (page 2 of 39)in EPIP-1.01 has been revised to satisfy your concern. The modified language in the EAL is not limited to the replacement of the acoustic monitoring indicator, but rather, takes into consideration any indication that a safety or relief valve failed to close after reactor coolant system pressure reduction.
Additional changes to the EAL reflect the results of the ongoing development of an EAL technical basis document. This procedure is provided for your information as Attachment 1.
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The EAL in the NAEP will be revised in the same manner in the next revision. provides the appropriate page of the NAEP, Appendix 10.11, as it will appear.
We would be pleased to discuss in detail any aspect of the revised portions of the EAL should you have any questions.
Very truly yours,
, y./ )
i I
j O'u L
W. L. Stewart Senior Vice President - Nuclear Attachments cc: Mr. William E. Cline, Chief Radiological Protection and Emergency Planning Branch Division of Radiation Safety and Safeguards
}
U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW Suite 2900 Atlanta, GA 30323 U. S. Nuclear Regulatory Commission (2 copies) 101 Marietta Street, NW Suite 2900 Atlanta, GA 30323 NRC Senior Resident inspector North Anna Power Station Mr. George O'N. Urquahart Chief, Radioitgical Emergency Response Planning Branch Department of Emergency Services 310 Turner Road Richmond, Virginia 23225-6491
ATTACHMENT 1
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